Rapid separation and purification of uranium and plutonium from dilute-matrix samples
- Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL). Nonproliferation Technology Section
This work presents a streamlined separation and purification approach for trace uranium and plutonium from dilute (carrier-free) matrices. The method, effective for nanogram quantities of U and femtogram to picogram quantities of Pu, is ideally suited for environmental swipe samples that contain a small amount of collected bulk material. As such, it may be applicable for processing swipe samples such as those collected in IAEA inspection activities as well as swipes that are loaded with unknown analytes, such as those implemented in interlaboratory round-robin or proficiency tests. Additionally, the simplified actinide separation could find use in internal laboratory monitoring of clean room conditions prior to or following more extensive chemical processing. We describe key modifications to conventional techniques that result in a relatively rapid, cost-effective, and efficient U and Pu separation process. We demonstrate the efficacy of implementing anion exchange chromatography in a single column approach. We also show that hydrobromic acid is an effective substitute in lieu of hydroiodoic acid for eluting Pu. Lastly, we show that nitric acid is an effective digestion agent in lieu of perchloric acid and/or hydrofluoric acid. A step by step procedure of this process is detailed.
- Research Organization:
- Savannah River Site (SRS), Aiken, SC (United States)
- Sponsoring Organization:
- USDOE
- Grant/Contract Number:
- AC09-08SR22470
- OSTI ID:
- 1169576
- Report Number(s):
- SRNS-STI-2013-00657
- Journal Information:
- Journal of Radioanalytical and Nuclear Chemistry, Vol. 300, Issue 2; ISSN 0236-5731
- Publisher:
- SpringerCopyright Statement
- Country of Publication:
- United States
- Language:
- English
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